ML20041F165
| ML20041F165 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/12/1982 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-82-175, NUDOCS 8203160249 | |
| Download: ML20041F165 (9) | |
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KANSAS GAS AND ELECTRIC COMPANY THE ELECT A C COMPANY GLENN L KOESTER f Q.
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. March 12, 1982
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,y Mr. Harold R. Denton, Director
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Office of Nuclear Reactor Regulation y
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 IC4LNRC 82-175 Re:
Docket Number STN 50-482 Subj : Additional Information
Dear Mr. Denton:
In discussions with Mr. Jon Hopkins, NRC Project Manager for the Wolf Creek Application, potentially open issues in the NRC's Safety Evaluation Report (SER) have been identified. The purpose of this letter is to provide information that should close several of the issues.
Attached are revised FSAR materials concerning:
- 1) A clarification of the major / minor procedure review for Wolf Creek (FSAR Section 13.5.1.2).
- 2) An update of liquid source terms to indicate the use of mixed bed resin in the recycle evaporator condensate i
domineralizer (FSAR Section ll.2.3a).
KG&E's response to NRC Question 240.1WC indicated that the FSAR would be revised to reflect wave runup at the ESWS Pumphouse. Attached are revisions to FSAR Section 2.4.10 which provide the additional information.
l This information will be formally incorporated into the Wolf Creek Gen-erating Station, Unit No. 1, Final Safety Analysis Report in Revision 9.
This information is hereby incorporated into the Wolf Creek Generating Station, Unit No.1, Operating License Application.
l l
8203160249 820312 Yours very truly, i
PDR ADOCK 05000482 b///(./ 4/)
d GLK: b 3
Attach cc:
Mr. J.B. flopkins (2)
/ l Mr. Thomas Vandel Mr. Eric Johnson l
201 N. Market - Wictuta, Kansas - Mail Address: PO Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451 L
J
OATH OF AFFIRMATION STATE OF KANSAS
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)~ SS:
COUNTY OF SEDGWICK )
I, Glenn L. Koester, of lawful age, being duly sworn upon oath, do depose, state and affinn that I am Vice President '- Nuclear' of Kansas Gas and Electric Company, Wichita,- Kansas, that I have signed the foregoing letter
' of transmittal, know the contents thereof, and that all statements contained therein are true.
KANSAS GAS AND ELECTRIC COMPANY By
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Glenn L. Koester b
Vice President - Nuclear W.B. Walker, Secretary J
4 4
i STATE OF KANSAS
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COUNTY OF SEIX; WICK. )
BE IT REFEMBERED that on this 12th day of March, 1982
, before i
me, Evelyn L. Fry, a Notary, personally appeared Glenn L. Koester, Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, l
who is personally known to me and who executed the foregoing instrument, and he duly acknoaledged the execution of the same for and on behalf-of and as the act and deed of said corporation.
,,..." "IN WITNESS WHEREOF, I have hereunto set my hand and affixed my seal the i,/t w,hl,klate'and year above written.
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5,. '. NO D V.b,! [
velyn[. Fry,Nofry
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1 My Commission expires on August 15, 1984.
I
SNUPPS-WC procedures for that activity.
The actual preparation of procedures may be performed by other KG&E personnel or by I
outside contractors, but the final responsibility lies with the designated responsible position.
Temporary changes can be made to approved procedures.
Tem-porary changes must be approved by a cognizant Group Leader and the responsible Section Supervisor.
At least one of these members shall have a Senior Reactor Operator license for all procedures affecting plant operation.
Procedures are classified by the Plant Safety Review Commit-tee (PSRC) as Safety-Related (SR) or Non-Nuclear Safety-Related (NNSR).
The SR procedures are further subdivided into Major and Minor procedures.
All procedures are reviewed and the reviews documented by qualified personnel.
All major SR procedures shall be reviewed by at least one individual other than the preparer, by the Plant Safety Review Committee (PSRC), and by the Plant Superintendent.
Review by the PSRC may be conducted and documented by indi-vidual members outside of formal meetings.
All minor SR procedures shall be reviewed by at least one individual other than the preparer.
All minor SR procedures will be reviewed by the full PSRC or a PSRC subcommittee.
If re-viewed by a PSRC subcommittee, the subcommittee will bring the minor SR procedure before the full PSRC for discussion l
and approval.
Temporary changes to major procedures which do not change the intent of the approved procedure revision may be made provided such changes are approved by the Cognizant Group Leader and one of the Duty and Call Supervisors.
At least one of these members shall have a Senior Reactor Operator license for all procedures affecting plant operation.
These I
changes shall subsequently be reviewed by the Plant Safety Review Committee (PSRC) and approved by the Plant Superin-tendent and shall then become permanent changes if appropri-ate.
Permanent changes to major procedures will be reviewed and approved as per the previous revision.
All temporary and permanent changes to minor SR procedures shall be approved by a cognizant group leader and reviewed and approved by the PSRC or an assigned subcommittee of the PSRC.
All temporary and permanent changes to NNSR proce-dures will be approved by a cognizant group leader and re-viewed and approved by the responsible section supervisor.
13.5.1.3 Procedures The Plant Superintendent will develop and implement station administrative procedures that provide a clear understanding of operating philosophy and management policies.
As stated Rev. 9 13.5-2
SNUPPS-WC in 13.5.1.2, administrative procedures will be implemented that provide methods for preparation, review and approval of all other station procedures including permanent procedures, temporary procedures or any procedures that might be of a transient or self-cancelling nature.
Administrative procedures will be developed that will pro-vide operations shift supervisors and shift crews with a clear understanding of how they are to conduct plant operations.
Included will be procedures that specifically describe who may manipulate the controls of the reactor and who may operate any apparatus c mechanism that might affect the reactivity of the reactor.
Procedures will be implemented specifying shift manning requirements which will be in accordance with the Technical Specifications.
The responsibilities and authorities of the supervising licensed personnel shall be delineated.
Rev. 9 13.5-2a
f SNUPPS-WC 11.2.3a CALCULATIONAL BASIS FOR LIQUID SOURCE TERMS
-The Wolf Creek Generating Station, Unit No. 1 will use the mixed bed demineralizer option shown in Itein 5 of Figure 11.1A-2 (Sheet 2) of the.SNUPPS FSAR.
The resulting GALE
. code input 'and annual liquid effluent releases are shown in Tables 11.2-8 and 11.2-9, respectively.
Rev. 9 11.2-2a
I SNUPPS-WC TABLE 11.2-8 GALE CODE INPUT DATA SNUPPS Nuclear Unit PWR Parameters value Thermal power level (megawatts) 3565.000 Plant capacity factor 0.800 Mass of primary coolant (thousands 1bs) 530.000 Percent fuel with cladding defects 0.120 Primary system' letdown rate (gpm) 75.000 Letdown cation demineralizer flow (gpm) 7.500 Number of steam generators 4.000 Total steam flow (millions Ibs/hr) 15.850 Mass of steam in each steam generator (thousands Ibs) 8.000 Mass of liquid in each steam generator (thousands 1bs) 104.000 Mass of water in steam generators (thousands 1bs) 416.000 Total mass of secondary coolant (thousands Ibs) 3570.000 Steam generator blowdown rate (thousands lbs/hr) 176.000 Primary to secondary leak rate (Ibs/ day) 100.000 Condensate demineralizer regeneration time (days) 17.500 Fission product carry-over fraction 0.001 Halogen carry-over fraction 0.010 Condensate demineralizer flow fraction 0.684 Radwaste dilution flow (thousands gpm) 5.000 Liquid Waste Inputs Collection Decay-Flow Rate Fraction Fraction Time Time Decontamination Factors Steam (gal / day) of PCA Discharged (days)
(days)
I Cs Others Shim bleed rate 1.84E+03 1.000
.1 20.9 2.0 1.00E*04 2.00E+04 1.00E+05 Equipment drains 3.00E402 1.000
.1 20.9 2.0 1.00E+04 2.00E+04 1.00E+05 Clean waste input 4.00E+02 -
.500
.1 10.0
.185 1.00E+04 1.00E+05 1.00E+05 Dirty waste input 1.14E+03
.058 1.0 7.0
.370 1.00E+04 1.00E+05 1.00E+05 S.G. blowdown 3.80E+05 (1)
.0
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.000 1.00E+03 1.00E+02 1.00E+03 Untreated blowdown 1.27E+05 (1) 1.0
.0
.000 1.00E+00 1.00E+00 1.00E+00 Regenerant solutions 1.71E+04 (1)
.0
.0
.350 1.33E+02 2.67E*02 1.33E+02 (1) Fraction of SCA internally calculated by GALE Code Gaseous Waste Inputs There is continuous low vol. purge of vol. control tk Holdup time for xenon (days) 9.0E+1 Holdup time for krypton (days) 9.0E+1 Fill time of decay tanks for the gas stripper (days) 0.0E+0 I
i Rev. 9
1 f
SNUPPS-WC TABLE 11.2-8 (Sheet 2)
Gas waste system:
particulate release fraction 1.0E-2 Primary leakage to buildings outside containment (1b/ day) 1.6E+2 Noncontainment:
iodine release fraction 1.0E-1 Particulate release fraction 1.0E-2 Containment volume (million cu ft) 2.5E+0 Containment atmosphere cleanup rate (thousand efm) 0.0E+0 Frequency of containment b1dg. high vol. purge (times /yr.)
2.4E+1 Containment-shutdown purge iodine release fraction 1.0E-1 particulate release fraction 1.0E-2
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Containment-normal purge rate (cfm) 4.0E+3 Containment-normal purge iodine release fraction 1.0E-1 particulate release fraction 1.0E-2 S team leak to turbine b1dg. (1bs/hr) 1.7E+3 1
Fraction iodine released from blowdown tank vent 0.0E+0 air ejector 3.0E-1 There is no cryogenic offgas system 3.0E-1 l
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SNUPPS-WC 2.4.10 FLOODING PROTECTION - REQUIREMENTS The flood design considerations are discussed in Section 2.4.2.2.
The plant buildings are not affected due to local intense precipitation at the plant site (Section 2.4.2.3).
All the safety-related buildings have their floor elevations above the level obtained by superimposing.the maximum wave runup on the PMF level in the cooling lake (Section 2.4.3).
The safety-related intake structure for the essential ser-vice water system is located at the edge of the cooling lake and is subjected to wave forces as well as high water.
The maximum wave runup elevation at the structure is 1100.2 feet with a wave height of 5.0 feet, and a wave period (maximum) of 3.3 seconds.
This wave runup elevation due to the maxi-mum wave is based on a vertical wall with an effective fetch that would exist without baffle dike A.
However, the intake structure for the essential service water system is designed to withstand a high water elevation of 1102.5 feet.
Therefore, the safety-related facilities are not affected by the PMF in the cooling lake or by the local intense precipi-tation at the plant site and no flood protection requirements are necessary.
2.4.11 LOW-WATER CONSIDERATIONS 2.4.11.1 Low Flow in Rivers and Streams Low-flow data of the regional rivers and streams were analyzed statistically for the frequency distribution.
The most severe drought of 1952-1957 was shown to have a recurrence interval of-50 years (Section 2.4.11.3).
Monthly flows in Wolf Creek for this once-in-50-years drought of 5-year duration were synthesized and are presented in Table 2.4-22.
The 5-year low flow to be expected in Wolf Creek is 1.6 cubic feet per second.
The analysis was based on a method described in Chow (1964, pages 18-10 to 18-15).
Low flows in the Neosho River during the same drought period are given in Table 2.4-23.
The 5-year duration low-flow rate was computed to be 147.5 cubic feet per second (Section 2.4.11.3).
2.4.11.2 Low Water Resulting from Surges, Seiches, or Tsunamis Consideration of low water conditions resulting from surges, seiches,' or tsunamis is not applicable to this site since there are no large bodies of water near the site, nor is the site near a coastal area.
Rev. 9 2.4-42 1